Sputter deposition and plasma modification of tungsten alloys for nuclear fusion applications
dc.contributor.author | Mahoney, Nicholas | |
dc.date.accessioned | 2025-05-13T05:55:19Z | |
dc.date.available | 2025-05-13T05:55:19Z | |
dc.date.issued | 2025 | |
dc.description.abstract | The ITER reactor aims to be first thermonuclear fusion device to demonstrate net fusion power. Critical plasma-facing components in the reactor will be made of tungsten, but helium plasma irradiation is known to embrittle tungsten metal. A future reactor will therefore need an alternative material to extend the lifetime of the components. This thesis investigated the use of tungsten alloy films as a plasma-facing material for a future reactor. Tantalum and chromium were chosen as the alloying elements, and 60 − 100 nm films were manufactured using magnetron sputter deposition at a variety of alloy concentrations. Tungsten alloy films are known to deposit in an undesirable A15 crystal phase. The films were heat treated at 650◦C for 1 hour, 2 hours and 4 hours to induce and investigate the phase transition from A15 to BCC structure. X-ray diffraction patterns confirmed the presence of an A15 structure prior to annealing. The A15 phase was very stable in comparison with past results, requiring over 2 hours at 650◦C to transition to BCC. This was speculated to be linked to oxygen trapped in the films during deposition. The phase transition was slower in alloyed films than a pure tungsten control, with the retarding effect of tantalum stronger than chromium, which suggested the alloying atoms further stabilised the deposited A15 structure. Resistivity of the films saw a reduction with annealing time characteristic of the phase transition. The annealed alloy films were then exposed to helium plasma in the Magnetised Plasma Interaction Experiment at 300◦C, 500◦C and 800◦C. Surface morphology changes were tracked with secondary electron imaging. At 800◦C, surface pits were seen, which were larger in a pure tungsten film than in low concentration alloy films. Advanced surface roughening was observed in the chromium films, while a high concentration tantalum film had no surface damage at all. X-ray diffraction patterns confirmed these trends, and showed an increase in microstrain with the surface roughening in the chromium alloys. These results suggest W-Ta alloy films may have superior irradiation resistance than W-Cr alloy films, but more work is needed to confirm the trends in alloy concentration. | |
dc.identifier.uri | https://hdl.handle.net/1885/733750337 | |
dc.subject | Nuclear Fusion | |
dc.subject | ITER | |
dc.title | Sputter deposition and plasma modification of tungsten alloys for nuclear fusion applications | |
dc.type | Thesis (Honours) | |
dcterms.valid | 2024 | |
local.contributor.affiliation | Research School of Physics, College of Science, The Australian National University | |
local.contributor.supervisor | Corr, Cormac | |
local.identifier.doi | 10.25911/7TC3-N437 | |
local.identifier.proquest | Yes | |
local.mintdoi | mint | |
local.type.degree | Other |
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